Monte Carlo study of the beam shaping assembly optimization for providing high epithermal neutron flux for BNCT based on D–T neutron generator

Hang, Shuang; Tang, Xiaobin; Shu, Diyun; Liu, Yuanhao; Geng, Changran; Gong, Chunhui; Yu, Haiyue; Chen, Da

doi:10.1007/s10967-016-5001-4

Cited by 12 publications

(5 citation statements)

References 26 publications

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“…However, in recent years, accelerator-based neutron beams are being developed with great enthusiasm worldwide to realize in-hospital BNCT treatment facilities. Therefore, in this work, a reactorbased BNCT neutron beam [14] and accelerator-based BNCT neutron beams using D-D [15], D-T [16] and p- 7 Li [17] reactions are employed to validate the performance of the designed epithermal neutron flux detector. The spectra of the employed BNCT neutron beams are shown in figure 2.…”

Section: Validation Of the Detector Performancementioning

confidence: 99%

The new design and validation of an epithermal neutron flux detector using ⁷¹Ga(n,γ)⁷²Ga reaction for BNCT

et al. 2019

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The epithermal neutron (0.5 eV-10 keV) flux is an essential characteristic for the boron neutron capture therapy (BNCT) neutron beam. The epithermal neutron flux measurement of a BNCT neutron beam is always a critical issue to its quality assessment and radiation dose evaluation. In this work, a cylindrical activation detector using 71 Ga(n, γ) 72 Ga reaction is designed by Monte Carlo simulations to determine the epithermal neutron flux of the BNCT neutron beam. In the detector, the activation material, i.e., gallium nitride (GaN) wafer, is positioned in the geometrical center of a high-density polyethylene (HDPE) cylinder covered with cadmium (Cd) foil. On completion of the design, the performance of the detector is validated by Monte Carlo simulations using reactor-and accelerator-based BNCT neutron beams. It is concluded from the performance validation results that the detector can accurately determine the epithermal neutron flux of the BNCT neutron beam. The designed epithermal neutron flux detector will be efficiently applicable to characterize the field of the BNCT neutron beam. K: Beam-line instrumentation (beam position and profile monitors; beam-intensity monitors; bunch length monitors); Instrumentation for neutron sources; Neutron detectors (cold, thermal, fast neutrons); Solid state detectors 1Corresponding author.

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Section: Validation Of the Detector Performancementioning

confidence: 99%

The new design and validation of an epithermal neutron flux detector using ⁷¹Ga(n,γ)⁷²Ga reaction for BNCT

et al. 2019

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“…Neutron sources that are widely used today are accelerators. The neutron beams produced from the accelerator are not appropriate for direct use in BNCT therapy, because their energy is too high and they still contain gamma radiations [4]. Therefore we need a beam processing system called the Beam Shaping Assembly (BSA).…”

Section: Introductionmentioning

confidence: 99%

Dose analysis of Boron Neutron Capture Therapy (BNCT) on head cancer using PHITS code with neutron source from accelerator

Bilalodin

Haryadi

Abdullatif

2023

J. Phys.: Conf. Ser.

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The dose analysis of Boron Neutron Capture Therapy (BNCT) on head cancer using the Particle and Heavy Ion Transport Code System (PHITS) has been carried out. The purpose of this study was determine the rate of dose received and the irradiation time required for head cancer therapy using the BNCT method. The research was conducted through a simulation approach. The PHITS code was used to design an epithermal neutron source derived from accelerator and to define the geometric dimensions of the head tissue components. The head model is based on Snyder’s head model with cancer cells located in the center of the brain at a depth of 3.8 cm. The investigation of the dose distribution on the head included skin, skull, brain and cancer sections consisting of Planning Target Volume (PTV), Clinical Target Volume (CTV) and Gross Tumor Volume (GTV). Simulations were carried out at boron concentrations of 30, 40, 50, 60, 70, and 80 μg/g tissue. Based on the simulation results, the greater the boron concentration, the greater the resulting dose rate. The highest dose rate was obtained in the GTV area of 6.37 x 10-2 Gy/s using a boron concentration of 80 μg/g tissue. The effective time for cancer therapy was calculated based on the highest dose rate obtained at 13,08 minutes.

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“…Neutron Generators (NG) are extensively used in the various industrial applications such as neutron radiography [1,2], neutron activation analysis [3][4][5], boron neutron capture therapy [6][7][8], explosive material detection [9,10] and material testing [11].…”

Section: Introductionmentioning

confidence: 99%

MCNP Dose evaluation around D-D and D-T neutron generators and shielding design

2021

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In recent years, neutron generators have extensively used as neutron sources and vast efforts have been made to develop high yield neutron generators, so the aspect of radiation shielding during the utilization of neutron generators is unavoidable. In this study, dose distribution around the D-D and D-T neutron generator was calculated by using Monte Carlo simulation. Then an effective shielding was designed and different materials with different thicknesses at distinction distances from the generator were examined. Finally, the organs dose was acquired by using ICRP 110 male phantom with and without shielding at different body position relative to generator tube.The results show that the dose induced by the D-T generator is 500 times greater than the D-D generator and the neutron dose is about 100 times more than gamma dose. The dose is reduced about 20 times by increasing the distance up to 5 m, however, the presence of Borated-Polyethylene with a thickness of 60 cm as most effective shielding reduces the whole-body dose up to 60%. Besides, inserting a layer of Pb to Borated-Polyethylene is effective to attenuate the gamma-rays. The received dose to organs depends on the body direction relative to tube head of neutron generator. In general, the best position of tube placement relative to shielding wall are 90 and 180 degrees for the D-T and D-D generators, respectively, distance between the generator tube head and the phantom is suggested 200 cm and it is recommended that for most dose reduction, the operator stands in the anterior-posterior position relative to generator tube. K: Dosimetry concepts and apparatus; Models and simulations; Radiation damage evaluation methods; Neutron sources

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Monte Carlo study of the beam shaping assembly optimization for providing high epithermal neutron flux for BNCT based on D–T neutron generator

Cited by 12 publications

References 26 publications

The new design and validation of an epithermal neutron flux detector using ⁷¹Ga(n,γ)⁷²Ga reaction for BNCT

The new design and validation of an epithermal neutron flux detector using ⁷¹Ga(n,γ)⁷²Ga reaction for BNCT

Dose analysis of Boron Neutron Capture Therapy (BNCT) on head cancer using PHITS code with neutron source from accelerator

MCNP Dose evaluation around D-D and D-T neutron generators and shielding design

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Monte Carlo study of the beam shaping assembly optimization for providing high epithermal neutron flux for BNCT based on D–T neutron generator

Cited by 12 publications

References 26 publications

The new design and validation of an epithermal neutron flux detector using 71Ga(n,γ)72Ga reaction for BNCT

The new design and validation of an epithermal neutron flux detector using 71Ga(n,γ)72Ga reaction for BNCT

Dose analysis of Boron Neutron Capture Therapy (BNCT) on head cancer using PHITS code with neutron source from accelerator

MCNP Dose evaluation around D-D and D-T neutron generators and shielding design

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The new design and validation of an epithermal neutron flux detector using ⁷¹Ga(n,γ)⁷²Ga reaction for BNCT

The new design and validation of an epithermal neutron flux detector using ⁷¹Ga(n,γ)⁷²Ga reaction for BNCT